Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Gamma and Neutron Dosimetry in Mixed Radiation Fields Using a Single Silicon Diode

Document Type : Research Paper

Authors

Hossein Zaki Dizaji
Feraydoon Abbasi Davani
Tayeb Kakavand
Abstract
During the past few years, real time gamma and neutron dosimeters have been developed and silicon diodes have frequently been used in these dosimeters. Silicon diodes are sensitive to gamma, and their neutron sensitivity is ensured with a converter layer on their front surfaces. In this study, a special converter detector design is optimized for dosimetry and determination of the neutron and gamma dose equivalent. Data analysis based on the pulse height is used for measuring the neutron and gamma dose equivalent. Neutron and gamma dose equivalent are determined in the energy range of 1-12MeV and 0.3-6MeV, respectively. The lower limit of dosimetry for gamma and neutron are 0.015μSv and 10μSv, respectively. In the 241Am-Be source radiation, a good agreement has been observed between the calculated and experimental measurements and the errors corresponding to gamma and neutron are less than 15% and 18%, respectively.

Keywords

Gamma and Neutron Dosimetry
Silicon Diode
Mixed Radiation Fields
Convertor Layer
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